US20220037043A1 - Reactor and safety method for a reactor for the event of a meltdown of the core - Google Patents

Reactor and safety method for a reactor for the event of a meltdown of the core Download PDF

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US20220037043A1
US20220037043A1 US17/443,991 US202117443991A US2022037043A1 US 20220037043 A1 US20220037043 A1 US 20220037043A1 US 202117443991 A US202117443991 A US 202117443991A US 2022037043 A1 US2022037043 A1 US 2022037043A1
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vessel
reactor
primary
steam generator
primary circuit
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Franck Morin
Gilles Avakian
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Commissariat a lEnergie Atomique et aux Energies Alternatives CEA
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Commissariat a lEnergie Atomique et aux Energies Alternatives CEA
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G21C9/02—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • G21C15/12—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from pressure vessel; from containment vessel
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/18—Emergency cooling arrangements; Removing shut-down heat
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • the invention relates to the field of safety of nuclear plants and more particularly the management of serious accidents of pressurised water nuclear reactors (PWR). Still more specifically, the present invention applies to the management of accidents involving the formation of a corium bath at the vessel bottom, following a serious accident occurrence situation, in the context of a strategy for keeping or retaining the corium in the vessel.
  • PWR pressurised water nuclear reactors
  • FIGS. 1 and 2 A PWR-type nuclear plant is illustrated in FIGS. 1 and 2 .
  • such a plant comprises a containment enclosure 600 inside which the reactor 1 is housed.
  • the reactor 1 comprises a vessel 10 forming, together with a cap 20 , a tight enclosure. This tight enclosure accommodates the fuel assemblies of the core 30 .
  • the core is represented by an area in dotted lines.
  • the vessel 10 further comprises at least one so-called cold fluid inlet 13 , connected to a primary circuit 100 and at least one so-called hot outlet 14 , also connected to the primary circuit 100 .
  • Pressurised water circulates in the primary circuit 100 .
  • the primary circuit 10 ensures the transport of heat from the core 30 towards a secondary circuit 200 inside which water also circulates.
  • the secondary circuit 200 comprises one and preferably several steam generator(s) 210 .
  • the heat exchange between the primary circuit 100 and the secondary circuits 200 is done inside the steam generators 210 .
  • a loop 214 of the primary circuit 100 is illustrated in the steam generator 210 .
  • FIGS. 1 and 2 illustrate other perfectly classical elements of a primary circuit 100 and of a reactor 1 core 30 such as: control rods 40 , a hydraulic pump 102 at the vessel 10 inlet to make water circulate in the primary circuit 100 , a pressuriser 110 at the vessel 10 outlet, a containment enclosure 600 , and structures forming a sill 601 and walls 602 delimiting a vessel 10 well 603 .
  • the fluid condenses in a condenser 230 before being injected again in the steam generators 210 by a pump 240 .
  • the condenser 230 is cooled down by an open circuit 300 fed by a water source 310 such as a river.
  • This circuit 300 also comprises lift pumps 320 , 330 and a cooling tower 340 .
  • the water of the primary circuit 100 is intended to extract calories generated by the reactor 1 in order to transfer them to the secondary circuit 200 , to transform them into electricity using an energy conversion system such as a turbo-generator.
  • the core 30 is critical, and the produced thermal power is evacuated by the primary circuit 100 . Monitoring of the criticality of the core is ensured by the position of the control rods 40 in the core 30 , but also by a content of water-soluble boron in the water of the primary circuit.
  • Corium is a partial or total set of molten fuels of vessel internals 10 in the molten state.
  • the corium flows by gravity into the bottom 12 of the vessel 10 and forms a bath therein.
  • the corium includes all or part of the molten fuel stock, containing all solid fission products and the residual thermal power associated thereto.
  • FIGS. 3A to 3C illustrate, in a very schematic way, a serious accident of a PWR vessel with the formation of a corium bath and then piercing of the vessel.
  • FIG. 3A the disaggregation and the partial meltdown of the core 30 , the formation of corium 70 and the apparition of a corium 70 bath 71 at the vessel 10 bottom 12 are illustrated.
  • a surface liquid metal layer 72 appears at the free surface of the bath 71 .
  • a portion of the thermal power of the corium 70 bath 71 is transmitted to this layer 72 .
  • FIG. 3B illustrates, in a very schematic way, the apparition of this metallic layer 72 (whose thickness is intentionally exaggerated for clarity).
  • the area bearing the reference A illustrates the beginning of piercing of the vessel 10 by the metallic layer 72 .
  • This piercing of the vessel 10 is caused by a phenomenon commonly called “focusing effect”.
  • the metallic layer 72 is a good heat conductor and absorbs a large portion of the thermal energy of the corium bath 71 .
  • the focusing effect corresponds to a situation in which the metallic layer 72 transfers a portion of its heat by conduction over a small surface of the lateral walls 11 of the vessel 10 . This thermal power focusing on a small surface could result in piercing of the walls 11 of the vessel 10 .
  • FIG. 3C illustrates the completion of piercing of the vessel 10 .
  • the corium 70 then spills out in the vessel 10 well 603 .
  • explosions called steam explosions (abrupt depressurisation of water and expansion of steam), and the creation of hydrogen.
  • Ex Vessel Retention There are two modes of management of the corium in the event of a Serious Accident in a PWR depending on the designers of the PWER nuclear boiler.
  • a first range of solutions referred to as Ex Vessel Retention, consists in letting the corium 70 pierce the vessel 10 , with the primary circuit depressurised, and flow in an area intended for spreading of the corium and for the management of cooling thereof.
  • This type of solutions has the drawback of requiring an impressive platform for the reception and spreading of corium called recuperator, which considerably weighs down the structure to be built and the infrastructure cost of the reactor enclosure.
  • recuperator which considerably weighs down the structure to be built and the infrastructure cost of the reactor enclosure.
  • Another major drawback relates to the demonstration of integrity of the third containment barrier formed by the reactor enclosure, to avoid the contamination of the environment, since the containment barrier formed by the primary circuit has been broken.
  • a second range of solutions referred to as In Vessel Retention or by its acronym IVR, consists in deploying systems for keeping the corium 70 inside the vessel 10 by avoiding piercing of the latter.
  • one strategy aims to keep the corium 70 in the vessel 10 and to extract its residual power through the wall of the vessel 10 by means of an external cooling, in particular through the set-up of a (natural or forced) convection loop, after soaking of the vessel 10 well 602 .
  • a natural circulation of water in contact with the vessel, and then vaporised and condensed again at the upper portion of the enclosure may also be set up.
  • This type of solutions is suggested for managing the evacuation of the residual power in the event of a serious accident in the AP1000 reactor of the company WestinghouseTM.
  • This cooling means is completely passive, in contrast with the solution described in the document WO2009/053322.
  • An IVR strategy described in the document FR2763168 or EP0907187 consists in providing a device for recovering the corium at the bottom of the vessel.
  • the corium flows by gravity from the core up to this recuperator.
  • it is provided for an injection of water by gravity by an additional tank connected to the vessel well.
  • This solution has the drawback of requiring the presence of an additional system formed by the recuperator, which weighs down and substantially enlarges the size of the reactor vessel.
  • the means for injecting water into the vessel formed by the tank directly connected to the primary circuit are only but a backup injection means complementary to those already present for the treatment of sizing accidents.
  • the residual primary pressure prevailing upon the occurrence of the serious accident requires providing for a considerable gravity height of this tank, which considerably weighs down the structure to be built.
  • the present invention aims such an objective.
  • Another objective of the present invention consists in reducing, and possibly eliminating, the risk of piercing of the vessel by focusing effect.
  • the present invention provides for a safety method for a pressurised water nuclear reactor for the event of a meltdown, at least partially, of a core of the reactor with the formation of a corium bath, the reactor comprising, during an operation phase, at least:
  • the method comprises at least the following step in response to a detection of an event characterising a meltdown, at least partially, of the core of the reactor with the formation of a corium bath in a bottom of the vessel and with the formation of a liquid metallic layer at the surface of the corium bath:
  • the pressurised secondary fluid typically water at saturation pressure and temperature, contained in the secondary circuit and in particular in the steam generator(s) flows into the bottom of the vessel over the metallic layer.
  • this coolant injection is performed in a passive way since the water of the secondary circuit is at a higher pressure than that of the primary circuit.
  • the pressure of the water contained in a steam generator is in the range of 60 to 70 bars, while that of the primary circuit is typically lower than 20 bars when a Serious Accident situation occurs.
  • the water of the secondary circuit starts coming into contact with the overmelting liquid metal layer causing a drastic reduction of the heat flow at the origin of the piercing by focusing effect.
  • All or part of the water from the secondary circuit vaporises on contact with the liquid metal layer and with the corium bath, by running off along the reactor vessel on the cold branch side, advantageously along a volume commonly called downcomer.
  • Water from the secondary circuit flows over a period that is long enough to cool down the liquid metal layer at least over the entire period during which this liquid metal layer has a thickness that is small enough to generate a risk of piercing of the vessel.
  • this flow it is possible to consider this flow as monitored.
  • the flow rate of the flow flowing over the liquid metallic layer has not to be very high.
  • One way for managing this flow rate and this duration of water injection from the secondary circuit into the vessel consists in accurately calibrating the section of the opened breach(es) between the secondary circuit and the primary circuit.
  • the flow rate of secondary water coming into the vessel is that corresponding to a breach with a diameter of about 20 mm and more generally between 10 and 30 mm.
  • All of the water contained in one or several steam generator(s) (GV) then progressively flows into the reactor vessel.
  • the typical value of the liquid flow rate coming into the primary circuit from the secondary circuit is about 5 kg/s. As a non-limiting example, this flow rate is more generally comprised between 2 kg/s and 10 kg/s. This value is drastically lower than all safety injections intended to soak the core.
  • the method according to the invention allows for a long duration of transfer of water from the GV towards the area of a potential piercing of the vessel by focusing effect, but also for a significant limitation of the steam created by the water/liquid metal interaction, which limits overpressure in the primary circuit.
  • the duration of water injection from the secondary circuit into the vessel is in the range of three hours and more generally between 30 min and 5 hours.
  • the duration of injection would last from about one minute to a few minutes.
  • the available amount of water per steam generator varies between 29 tons and 70 tons per steam generator for a reactor having a power of 1300 MWe (the French Palier N4 type).
  • the time during which water from the secondary circuit flows over the corium bath is short when implementing the method according to the invention.
  • the time period during which the focusing effect could cause piercing of the vessel is relatively limited. It has been observed that the risk of piercing due to the focusing effect corresponds to a time interval where the corium bath has a liquid metallic layer at the surface with a relatively small thickness, typically of few centimetres. In this configuration, a large portion of the thermal power derived from the corium bath is transmitted to this thin metallic blanket, which power is then transmitted by contact to the inner wall of the vessel, and induces the progressive piercing of the latter.
  • the corium bath continues to be fed by the inner elements of the vessel which progressively melt down, and the liquid metal layer at the surface thickens, because of the stock of molten metal that increases.
  • the contact surface between the liquid metal layer and the inner wall of the vessel increases.
  • the thermal power transmitted to this later is then distributed across a larger thickness of the liquid metallic layer, and the vessel piercing power is then less concentrated. The risk of vessel piercing then becomes lower.
  • the thickness of the surface metallic layer is then such that the thermal power at the periphery and in contact with the vessel is no longer sufficient to pierce the vessel.
  • the external cooling of the vessel is sufficiently effective to evacuate the thermal power derived from the bath. Piercing of the vessel is then definitely stopped.
  • the flow is then reduced by so much and the external cooling then becomes sufficient to stop the progress of piercing of the vessel since the entire thermal power derived from the bath is evacuated up to the external water, without causing a meltdown of the vessel metal.
  • each kilogram of water per second that evaporates induces a cooling of the liquid layer by about 2 to 3 MWth.
  • cooling of the liquid metal layer corresponds to an evacuation of thermal power of about 10 to 15 MWth over three hours, which drastically reduces and even prevents piercing of the vessel.
  • the liquid metal layer at the surface comes into contact with the core support plate, illustrated in FIGS. 2 and 3A by the reference 17 .
  • the temperature of the liquid metal overheated by the thermal power of the corium bath is then drastically reduced by the significant meltdown of the lower portion of the core support plate. Indeed, the melting point of the metal is well below that which is likely to be reached by the liquid metal layer thereby causing the focusing effect.
  • the invention does not require any additional components in the reactor, such as a recuperator, or additional systems in the vessel well, such as forced convection means.
  • the invention does not require any additional tanks placed at a substantial height. Yet, by taking advantage of the pressure of the secondary circuit, the invention allows for a very quick water injection.
  • the suggested solution allows for a passive operation, that is to say without any pump to pour a coolant over the corium bath, an enhancement of the strategy for managing the corium within the vessel, by fighting the effects of the Focusing Effect likely to jeopardise the success in preventing piercing of the reactor vessel.
  • the invention does not provide for additional components or for tappings directly on the reactor vessel, these might cause a reduction of the reliability of the reactor safety.
  • the invention allows considerably enhancing the safety of a pressurised water reactor in the event of a meltdown of the core with the formation of a corium bath.
  • the invention also covers a pressurised water nuclear reactor comprising at least:
  • the reactor comprises a safety system which comprises a safety device comprising at least one explosive device configured so as to explode in order to break up the fluidic insulation between the secondary circuit and the primary circuit so as to create at least one, and preferably only one passage enabling a flow inside the primary circuit of the secondary fluid present in the at least one steam generator.
  • a safety system which comprises a safety device comprising at least one explosive device configured so as to explode in order to break up the fluidic insulation between the secondary circuit and the primary circuit so as to create at least one, and preferably only one passage enabling a flow inside the primary circuit of the secondary fluid present in the at least one steam generator.
  • the explosive device is configured so as to explode in the event of a meltdown, at least partially, of the core with the formation of a corium bath in a bottom of the vessel and with the formation of a liquid metallic layer at the surface of the corium bath.
  • the exposure of the explosive device enables the secondary fluid contained in the at least one steam generator to flow in the vessel while passing beforehand through the primary circuit.
  • the pressurised secondary fluid contained in the steam generator spills out in the primary circuit, advantageously in the cold branch(es), and then in the vessel. This fluid cools down the liquid metallic layer, which attenuates the focusing effect phenomenon. Thus, piercing of the vessel is avoided.
  • S breach is the minimum section of said passage that enables the injection, inside the primary circuit, of the secondary fluid present in the at least one steam generator.
  • S breach is smaller than 20 cm 2 (10 ⁇ 2 meters).
  • S breach is larger than 2 cm 2 , and preferably S breach is larger than 3 cm 2 . According to one example, S breach is comprised between 2 cm 2 and 20 cm 2 .
  • S breach is comprised between 0.2 cm 2 and 20 cm 2 , preferably 0.8 cm 2 and 20 cm 2 and still more preferably between 2 cm 2 and 7 cm 2 .
  • the inlet section on the cold branch side of the reactor vessel is much larger than the section of the breach created between the secondary circuit and the primary circuit.
  • S breach ⁇ 0.05*S inlet preferably S breach ⁇ 0.01*S inlet , preferably S breach ⁇ 0.005*S inlet and preferably S breach ⁇ 0.001*S inlet
  • S inlet is the minimum section of the passage of the primary fluid in the primary circuit and up to the vessel.
  • the section S inlet is the sum of the sections of the inlets of the primary circuit up to the vessel.
  • the passage section of the primary fluid on the cold branch side is in the range of 6000 cm 2 .
  • S inlet has a circular section
  • S inlet has a diameter comprised between 800 and 900 mm (10 ⁇ 3 meters).
  • the section through which the secondary fluid flows into the primary circuit is much smaller than the section through which the primary fluid usually flows in the vessel.
  • This ratio of the sections S breach and S inlet allows injecting into the primary and therefore into the vessel a secondary fluid flow over a relatively long time period. More specifically, over a time period that is long enough to cover the duration during which the thickness of the liquid metallic layer is small enough to pierce the wall of the vessel by focusing effect.
  • FIG. 1 schematizes a PWR-type nuclear plant.
  • FIG. 2 schematically illustrates a vertical section of a PWR-type reactor vessel in its vessel well in an operating state excluding a serious accident situation.
  • FIGS. 3A to 3C schematically illustrate different phases of a serious accident resulting in the partial or total meltdown of the core, the formation of a corium bath and then piercing of the vessel in the reactor illustrated in FIG. 2 by focusing effect.
  • FIG. 4 schematically illustrates the implementation of the invention with cooling of the corium bath by injection of water from the secondary circuit through the primary circuit up to the bottom of the vessel.
  • FIGS. 5A and 5B schematically illustrate a PWR-type nuclear plant integrating a safety system according to a first embodiment of the invention.
  • FIG. 5B illustrates, in an enlarged view, the hydraulic connections between the vessel and the steam generator.
  • FIGS. 6A to 6C are detail views of a non-limiting example corresponding to the first embodiment represented in a more general way in FIGS. 5A and 5B enabling the injection, within a steam generator, of secondary water inside the primary circuit.
  • FIG. 7 is a diagram illustrating the operation of the invention in a perspective view of a solution implementing the embodiment illustrated in FIGS. 5A and 5B .
  • FIG. 8 illustrates, in a very schematic way, a vessel portion and the parameters allowing positioning fuses along a generatrix of the vessel.
  • said detection of the formation of a liquid metallic layer at the surface of the corium bath is performed using at least one fuse disposed on a wall of the vessel, the at least one fuse being configured so as to melt down when the liquid metallic layer reaches it.
  • the reactor comprises several fuses distributed according to at least one generatrix of a wall of the vessel so that two neighbouring fuses define a vessel slice, the volumes V slice of the slices being identical.
  • setting of the secondary circuit in communication with the primary circuit is triggered according to the detection, for example using at least one fuse, of a temperature of the inner wall of the vessel higher than a temperature threshold Tf, with Tf higher than 400° C. and preferably Tf higher than 500° C.
  • a profile of the evolution of the height of the liquid metallic layer in the vessel is determined by means of fuses disposed over an inner wall of the vessel and preferably disposed according to at least two generatrices of this wall. The time point at which the secondary circuit is set in fluidic communication with the primary circuit is determined according to this profile.
  • a series of fuses is disposed over an inner face of the wall of the vessel.
  • the fuses are placed over a generatrix of the bottom of the vessel and of a lateral wall of the vessel. The progress of the corium level rise, as well as the beginning of degradation of the vessel by the liquid metal layer at the surface thereof is detected by the successive deactivation of the fuses of this generatrix. Starting from a determined corium height, the activation of the fluidic communication is activated.
  • the reactor comprises at least one fuse over a wall of the vessel.
  • the fuse is configured so that, when the liquid metallic layer reaches the fuse, it makes the latter melt down.
  • the reactor comprises several fuses distributed according to at least one generatrix of a wall of the vessel.
  • the fuses are disposed along a generatrix so that if the volume of the liquid metallic layer increases at a constant rate, the time intervals separating the time points at which two successive fuses of a generatrix are reached by the liquid metallic layer remain constant.
  • the secondary fluid flows inside the vessel over the liquid metallic layer at least over the entire period during which the liquid metallic layer has a thickness e 72 that is small enough to pierce at least partially an inner wall of the vessel.
  • the secondary fluid flows inside the vessel over the liquid metallic layer during at least thirty minutes and preferably during at least one hour and preferably during at least two hours.
  • the secondary water flow runs in the primary circuit throughout a passage whose minimum section S breach is comprised between 0.2 cm 2 (0.2 ⁇ 10 ⁇ 4 m 2 ) and 20 cm 2 and preferably between 0.8 cm 2 and 7 cm 2 . If the minimum section S breach of this passage is circular, then its diameter is comprised between 5 and 50 mm and preferably between 10 and 30 mm. Typically, this diameter is about 20 mm.
  • the secondary fluid flows inside the vessel ( 10 ) with a flow rate lower than 10 kg/s (10 3 grams/second) and preferably lower than 7 kg/s.
  • the reactor comprises an inner envelope, located inside the vessel, enveloping the core and defining with an inner wall of the vessel an annular volume called downcomer, the downcomer being configured so that, during the normal operation of the reactor:
  • the reactor is configured so that when the explosive device creates the at least one passage suppressing the fluidic insulation between the secondary circuit and the primary circuit, the secondary fluid contained in the steam generator then flows in a bottom of the vessel while passing beforehand through said inlet of the vessel and then through the downcomer.
  • This embodiment promotes a run-off of the secondary water over the inner walls of the vessel. This allows cooling down the liquid metallic layer even more effectively than in the case where the secondary fluid penetrates into the vessel from the outlet of the latter, or on the hot branch side, and therefore without passing through the downcomer. Indeed, by running off on the downcomer side, the evaporation of the secondary water, and therefore cooling of the liquid metal layer, takes place in the area where piercing of the vessel is located. To reach this embodiment, the connection on the secondary side should be performed on the cold branch side of the steam generator, that is to say on the heat-exchanger side where the primary temperature corresponds to the cold return of the primary circuit (cold water box).
  • the reactor comprising several fuses distributed according to at least one generatrix of a wall of the vessel, the fuses are distributed along a generatrix so that two neighbouring fuses according to this generatrix, define a vessel slice, the volumes Vslice of the slices are identical.
  • the steam generator comprises an envelope enclosing the secondary fluid and the primary fluid, the envelope enclosing an insulation fluidly isolating the secondary and primary fluids, the safety system being configured so as to suppress the insulation between the secondary and primary fluids inside the envelope of the steam generator, thereby creating said passage.
  • the suppression of this insulation corresponding to a breach with a limited and monitored diameter (typically 20 mm in diameter).
  • the steam generator comprises tubes inside which the primary fluid circulates, the secondary fluid being in contact with an outer wall of the tubes, the safety system comprising an explosive device including at least one explosive plug accommodated inside at least one of said tubes and a triggering device, the explosive plug being configured so as to explode, when it is triggered by the triggering device, so as to section at least the tube in which it is accommodated, thereby creating said passage.
  • the plug forms, at least partially and advantageously on its own, said fluidic insulation between the secondary and primary circuits.
  • the steam generator comprises:
  • the safety system comprising:
  • the explosive plug is configured so as to explode, when it is triggered by the triggering device, so as to destroy itself at least partially to enable a circulation through said channel thereby forming a passage between the first and second portions.
  • the plug forms, at least partially and advantageously on its own, said fluidic insulation between the secondary and primary circuits.
  • the triggering device is configured so as to be activated from outside the steam generator.
  • the triggering device comprises at least one wire crossing a wall of the envelope of the steam generator.
  • the triggering device comprises:
  • the safety device is configured so that the secondary fluid contained in the steam generator flows in the vessel with a flow rate comprised between 4 and 5 kg/s for a pressure of the steam generator in the range of 68 bar.
  • the focusing effect phenomenon could be slowed down and the piercing of the vessel could be avoided.
  • a normal operation of the reactor 1 or of the plant refers to an operating phase in the absence of accidents or serious accidents.
  • An accident such as a primary coolant loss, a large breach or a very large breach accident does not represent a normal operation phase of the reactor 1 .
  • FIG. 4 illustrates a reactor 1 , for example of the same type as that described with reference to FIGS. 2 to 3A .
  • the core 30 is molten or partially molten.
  • a corium 70 bath 71 has formed in the bottom 12 of the vessel 10 .
  • the liquid metal layer 72 has formed or is about to form.
  • this liquid metal layer 72 Before this liquid metal layer 72 starts piercing the vessel 10 or rapidly after the beginning of this partial piercing, it is provided to pour a cooling fluid in the bottom 12 of the vessel 10 , and therefore over this layer 72 .
  • This cooling fluid arrives from the inlets 13 and/or the outlets 14 of the primary circuit 100 .
  • this cooling fluid consists of water from the secondary circuit 200 which flows in the primary circuit 100 .
  • a depressurisation of the primary circuit 100 is triggered. This may be performed by opening a specific valve located for example at the top of the pressuriser 110 . This depressurisation of the primary circuit might be triggered once a threshold temperature is reached, for example a temperature of the assembly sleeve that would reach 650° C. or more. This depressurisation of the primary circuit 100 results in the latter having a pressure lower than that of the secondary circuit 200 . Typically, the pressure in the depressurised primary circuit 100 is lower than 20 bars. By the effect of the pressure difference between the primary 100 and secondary 200 circuits, the communication of these circuits 100 , 200 causes a quick injection of the fluid of the secondary circuit 200 into the primary circuit 100 .
  • the fluid 800 of the secondary circuit 200 spills out into the primary circuit 100 and reaches the interior of the vessel 10 through the inlet 13 .
  • the reactor 1 comprises an inner envelope 15 , located inside the vessel 10 , enveloping the core 30 and defining together with the inner wall 11 of the vessel 10 an annular volume, commonly called downcomer 16 (descending portion).
  • This inner envelope 15 is configured so that, during the normal operation of the reactor 1 (that is to say in the absence of a serious accident for example):
  • the cold fluid of the primary circuit 100 penetrates into the reactor 1 through the inlet 13 ; descends by gravity in the downcomer 16 to reach the bottom 12 of the vessel, rises inside the envelope 15 while passing through an aperture plate commonly called support plate 17 ; crosses the core 30 to extract heat derived from the fission and comes out of the reactor 1 through the outlet 14 .
  • the cooling fluid derived from the secondary circuit 200 and which penetrates 801 into the vessel 10 via the circuit 100 therefore also descends along the wall 11 of the vessel 10 and reaches the liquid metal layer 72 .
  • this safety cooling fluid follows the natural route of water in the reactor 1 .
  • This cooling fluid comes into contact with the surface of the liquid metal layer 72 .
  • the cooling fluid reaches the liquid metal layer 72 at the most critical location, i.e. at the interface between the latter and the wall 11 of the vessel 10 .
  • the cooling fluid ensures a cooling function over the entire periphery where the liquid metal layer 72 is likely to pierce the inner wall 11 of the vessel 10 by focusing effect.
  • a cooling fluid supply from the downcomer 16 provides a particularly effective solution to reduce the risk of piercing of the vessel by focusing effect.
  • this mode of contacting liquid water with the overmelting metal layer 72 is performed by run-off from the inner wall of the vessel 10 , which is much softer than a heavy injection of water onto the corium bath.
  • a heavy injection of water onto the corium bath could cause a steam shock which is detrimental to the integrity of the vessel of the reactor.
  • the cooling fluid is represented in the form of a body 802 spread over the free surface of the metallic layer 72 . Naturally, when the latter is still not cooled down enough, the cooling fluid vaporises on contact with the metallic layer 72 .
  • the depressurisation of the primary circuit 100 facilitates the injection of the cooling fluid from the secondary into the vessel 10 .
  • this cooling fluid allows cooling down the liquid metal layer 72 when the latter has a thickness e 72 that is thin enough to concentrate the thermal power of the bath 72 on a too reduced surface such that it could pierce the inner wall 11 of the vessel 10 .
  • a cooling of the outer wall of the vessel 10 As illustrated in FIG. 4 , it is also provided for a cooling of the outer wall of the vessel 10 .
  • a cooling of the outer wall of the vessel 10 For this purpose, it is possible to soak the well 603 of the vessel 10 , i.e. water is injected or poured between the vessel 10 and the well 603 .
  • This cooling is usually sufficient in case of an IVR-type (in-vessel retention) accident, yet naturally not if the focusing effect phenomenon appears.
  • cooling from outside the vessel by soaking the well 603 of the vessel 10 allows, for example, extracting 1 Megawatts per square meter (1 MW/m 2 ). In a focusing effect situation, this cooling is no longer enough, since it is necessary to be able to extract 1.5 MW/m 2 , and even 2 MW/m 2 , in the area in which the focusing effect creates a piercing of the vessel 10 .
  • a tank for example in the fuel loading pool.
  • This tank could be used in the building of the reactor or outside the latter.
  • at least one portion of this tank shall be disposed high enough with respect to the vessel 603 to enable a flow into the latter by gravity.
  • at least one portion of this tank shall be located above the cap or cover 20 of the reactor 1 .
  • the flow rate of the cooling fluid derived from the secondary circuit 200 is not monitored.
  • modelling of this flow rate can be easily computed once the pressure of the secondary circuit 200 , and optionally of the primary circuit 100 , is known. It is primarily the initial water stock of the steam generators 210 , and the section S breach of the passage(s) between the secondary circuit 200 and the primary circuit 100 that determines the cooling duration. The calculations show that a quite limited portion of this total stock of the steam generators 210 is enough to sufficiently cool down the overmelting metallic layer 72 , and avoid piercing of the vessel 10 , while the metallic layer 72 at the surface sufficiently thickens.
  • the safety device is configured so that the passage section S breach of the passage(s) between the secondary circuit 200 and the primary circuit 100 enables the secondary water to come into the vessel 10 with a flow rate lower than 10 kg/s and preferably lower than 7 kg/s.
  • this flow rate is comprised between 4 and 5 kg/s for an initial pressure (that is to say before opening of the passage(s) towards the primary circuit 100 ) in the steam generator (GV) in the range of 68 bar.
  • S breach is smaller than 20 cm 2 (10 ⁇ 2 meters).
  • S breach is larger than 2 cm 2 .
  • S breach is comprised between 2 cm 2 and 20 cm 2 .
  • it is comprised between 2 cm 2 and 7 cm 2 .
  • S inlet is the minimum passage section between the primary circuit 100 and the inlet 13 of the vessel 10 . Typically, it therefore consists of the minimum section for the passage of the primary fluid during normal operation of the reactor. For example, S inlet corresponds to the section of the inlet 13 in the vessel. This section is illustrated in FIG. 8 . If there are several inlets of the primary circuit 100 in the vessel 10 , for example as illustrated in FIG. 7 , then S inlet is the sum of all inlets of the vessel 10 .
  • S breach is the section of the passage, or the sum of the sections of the passages when there are several passages, setting the secondary fluid present in the at least one steam generator 210 in fluidic communication with the primary circuit 100 .
  • the inlet section on the cold branch side of the reactor vessel is much larger than the section of the breach created between the secondary circuit and the primary circuit.
  • S breach ⁇ 0.05*S inlet and preferably S breach ⁇ 0.01*S inlet and preferably S breach ⁇ 0.005*S inlet are typically used.
  • the passage section of the primary fluid on the cold branch side is in the range of 6000 cm 2 .
  • the pressure of the water contained in a steam generator 210 is in the range of 60 to 70 bars.
  • the primary circuit 100 is depressurised. Indeed, devices for opening valves at the level of the pressuriser 110 are actuated to depressurise the primary circuit 100 , should a serious accident arise. This allows avoiding ejections of fission products of the core under pressure in case of piercing of the vessel. Moreover, this depressurisation of the primary circuit allows facilitating the injection of the secondary inside the vessel 30 .
  • triggering of the safety device is performed by an operator.
  • fuse(s) 900 disposed over the wall of the vessel 10 . These are configured so as to melt down when a threshold temperature Tf is applied to these fuses 900 . Typically, this temperature Tf is reached when corium forms in the vessel 10 and comes into contact with the fuses 900 . When the temperature within the vessel corresponds to the normal operation of the reactor, the fuses 900 do not melt down. According to one example, Tf>400° C., preferably Tf 500° C., preferably Tf ⁇ 600° C.
  • the fuse comprises a core made of an electrically-conductive material and a sheath which is electrically-insulating. Thus, a short-circuit between the metallic vessel and the conductive core is avoided.
  • the core is made of a metal such as aluminium whose melting point is close to 600° C., or of antimony.
  • the insulating sheath is made of a ceramic.
  • the fuse forms a cable having two ends connected to the safety device and an elbow located between these two ends.
  • the elbow corresponds to the lowermost point of the fuse.
  • the fuse is positioned on the inner wall 11 of the vessel 10 .
  • This allows enhancing the reliability of the detection of the apparition of the Focusing effect.
  • the temperature measurement will essentially depend on the boiling temperature of water in contact with the wall of the vessel, which does not allow effectively detecting the rise of the corium bath, as well as the formation of the Focusing Effect layer.
  • the safety device comprises a series of fuses 900 positioned along at least one generatrix of the inner wall 11 of the vessel 10 .
  • the fuses are positioned along at least two generatrices.
  • fuses placed at the upper portion might be reached and not characterise the progressive rise of the corium bath at the bottom of the vessel.
  • a series of fuses 900 is disposed over a generatrix of the hemispherical portion forming the bottom 12 of the vessel 10 , the latter and another portion of the fuses is disposed over a lateral wall of the vessel 10 .
  • These fuses allow determining the time point at which the corium bath 71 starts forming as well as the time point at which water from the secondary should be injected into the primary circuit 100 .
  • the profile of evolution of this temperature also allows detecting the rise of the corium level in the vessel 10 .
  • This profile also allows detecting the beginning of piercing of the latter by the liquid metal layer 72 .
  • fuses 900 of the same generatrix or for fuses 900 of two different generatrices, having different melting temperatures.
  • the fuses 900 it is desired to position corium bath height detectors so that the rate of rise of the corium bath is revealed by the fuses. This allows monitoring more accurately the time point at which the focusing effect could occur and the time point at which the fluid of the steam generators 210 should be poured into the primary circuit 100 .
  • this positioning of the fuses 900 is performed so that the volumes V slice of the core slices located between two consecutive or neighbouring fuses 900 are constant.
  • two neighbouring fuses according to a vertical distribution define a vessel slice.
  • This vessel slice is delimited, on the one hand, by the inner wall 11 of the vessel 10 and, on the other hand, by two vertical planes, each vertical plane passing through one of these neighbouring fuses 900 .
  • At least some, preferably all, of the volumes of the vessel slices are identical.
  • the neighbouring fuses according to a vertical distribution are disposed according to the same curve preferably forming a generatrix of the vessel 10 .
  • FIG. 8 shows, in a very schematic way, a portion of the vessel 10 , as well as fuses 900 disposed according to a generatrix G.
  • the fuses 900 define slices with substantially equal volumes V slice .
  • the fusible detectors are placed along 2 to 4 generatrices evenly distributed around the axis of the hemispherical bottom of the vessel 10 .
  • generatrices For a number of generatrices equal to 2, 3 and 4 respectively, these generatrices will be separated by an angle of 180°, 120° and 90° respectively.
  • the bottom of the vessel 10 is formed by a sphere portion, the sphere having a 4-meter diameter.
  • corium bath height detectors corresponding to 3, 6, 9, 12 and 15 m 3 of spilled corium. This allows determining the profile of the corium bath rise. By having a clear picture of the variation of the rate of rise of the corium bath, the operator (or the automatic safety device) could determine which time is the most appropriate to trigger the injection of water of the steam generators 210 into the primary circuit 100 .
  • the total filling of the hemispherical bottom is 16.75 m 3 .
  • the plane P corresponds to the junction between the hemispherical portion of the vessel and the lateral walls of the vessel extending according to a cylinder.
  • the volume V cap of the hemispherical portion of the cube could be calculated according to the following equation:
  • V c ⁇ a ⁇ p ⁇ ⁇ h 2 ⁇ ( 3 ⁇ R - h ) 3
  • the position of a fuse may be determined according to the value L arc calculated according to the following equation:
  • the fuses may be disposed in the following manner in order to have a correspondence between the rise speed of the corium bath, and the meltdown of these fuses:
  • this duration D1 is about one hour.
  • k1 is comprised between ⁇ 5 minutes and 15 minutes.
  • the passage section of the passage(s) between the secondary circuit 200 and the primary circuit 100 is dimensioned so as to enable pouring, between the time points t1 and t2, a flow rate Qmin that is sufficient to cool down the liquid metal layer 72 .
  • the fluid 800 derived from the secondary circuit and which is poured over the overmelting metal layer 72 descends by running off along the wall 11 of the vessel 10 .
  • this fluid 800 reaching the inside of the vessel 10 by penetrating into the latter through the outlet orifice 14 .
  • FIGS. 5A to 7 illustrate different embodiments allowing injecting the fluid of the secondary circuit 200 into the vessel 10 , via the primary circuit 100 .
  • the solutions of all these embodiments consist in setting the secondary circuit 200 in communication with the primary circuit 100 .
  • This communication is performed thanks to a safety system configured so as to break up intentionally a containment barrier that isolates these two circuits 100 , 200 .
  • a safety system configured so as to break up intentionally a containment barrier that isolates these two circuits 100 , 200 .
  • FIGS. 5A to 7 A first embodiment is illustrated by FIGS. 5A to 7 .
  • the hydraulic connection between the secondary circuit 200 and the primary circuit 100 consists of a hydraulic connection internal to the steam generators 210 .
  • a steam generator 210 forms an enclosure which encloses the fluid of the secondary circuit 200 and at the same time encloses at least one pipe 214 through which the fluid of the primary circuit 100 circulates. Thus, the fluid of the secondary circuit 200 comes into contact with an outer wall of the pipe 214 .
  • the safety system comprises a device which allows creating at least one breach between the inside of said pipe 214 and the fluid of the secondary circuit 200 present in the enclosure of the steam generator 210 .
  • the breach forms said passage enabling the injection of the secondary water into the primary circuit 100 .
  • FIG. 5B This solution is schematically illustrated in FIG. 5B . It will be described in detail, in the form of several variants, with reference to FIGS. 6A to 7 .
  • FIG. 6A illustrates a lower portion of the steam generators 210 .
  • This steam generator 210 comprises an envelope 260 with a generally cylindrical shape.
  • This envelope 260 defines an upper portion 211 , having openings 211 b , 211 b ′ in communication with the secondary circuit 200 and a lower portion 212 having openings 212 b , 212 b ′ in communication with the primary circuit 100 .
  • the upper 211 and lower 212 portions are separated by a plate 213 with tubes.
  • a lower face of the plate 213 with tubes delimits with the lower portion 212 a volume forming a water box.
  • the water box has a hemispherical shape. It is separated into two portions 212 a , 212 a ′ by a partition 2121 .
  • the portion 212 a has an opening 212 b hydraulically connected to the inlet 13 of the vessel 10 .
  • the portion 212 a ′ has an opening 212 b ′ hydraulically connected to the outlet 14 of the vessel 10 .
  • the portions 212 a and 212 b , as well as the tubes 214 are part of the primary circuit 100 .
  • the plate 213 with tubes carries a plurality of tubes 214 one end of which opens into the portion 212 a ′ and another end of which opens into the portion 212 a .
  • these tubes 214 for inverted “U” shapes. These “U”-shaped tubes are soaking in the water of the secondary circuit 200 present in the upper portion 211 of the steam generator 210 .
  • the pressurised hot water circulates, starting from the portion 212 a ′ firstly from the bottom to the top, up to the top of the “U” elbow, and then from the top to the bottom to reach the portion 212 a of the water box.
  • the water circulating in the tubes 214 transfers heat to the fluid of the secondary circuit 200 present in the upper portion 211 of the steam generator 210 .
  • the water could then escape via the outlet 212 b and return back to the inlet 13 of the vessel 10 to be heated up again by the core 30 .
  • each of the portions 212 a , 212 a ′ of the water box is provided with a hatch opening 2122 closed by a plug 2123 .
  • This hatch opening 2122 has a dimension that is large enough to enable a human or a robot to access the inside of the water box.
  • the safety system comprises a device, also called member, configured so as to break up the insulation between the primary circuit 100 and the secondary circuit 200 inside the steam generator 210 .
  • this device is an explosive device 216 configured so as to generate an explosion capable of creating a breach intentionally breaking up the hydraulic containment barrier between the primary circuit 100 and the secondary circuit 200 .
  • this breach is created in the so-called cold portion of a pipe 214 , that is to say downstream of the inverted “U” elbow. This allows facilitating the flow of the secondary fluid by gravity in the primary circuit 100 .
  • this breach is preferably located as low as possible according to a vertical axis, that is to say ideally immediately proximate to the plate with tubes 213 , that being so in order to favour a flow by gravity of all of the secondary water contained in the steam generator 210 .
  • this device bearing the reference numeral 216 in FIG. 6B , comprises an explosive plug 216 a accommodated inside a tube 214 ′.
  • this tube 214 ′ is identical to the tubes 214 of the plate 213 with tubes, which considerably simplifies the manufacture of the steam generator 210 .
  • the explosive plug 216 a is inserted into the tube 214 ′, above the plate 213 with tubes. When activated, the explosive plug 216 a sections at least the tube 214 ′ in which it is accommodated. The inside of this tube 214 ′ is then in fluidic communication with the water of the secondary circuit 200 present in the upper portion 211 of the steam generator 210 .
  • This water then spills out rapidly into the water box, and then into the primary circuit 100 , to reach the vessel 10 and the core 30 of the reactor 1 .
  • This water is rapidly directed into the reactor 1 by the effect of pressure prevailing in the steam generator 210 .
  • the steam generator 210 is hydraulically isolated very quickly in the event of an accident, thereby trapping the water masses contained therein and preserving therewithin the pressure prevailing therein.
  • the section S breach is substantially equal to the section of the tube 214 that has been sectioned if several tubes 214 are sectioned S breach is substantially equal to the sum of the sections of the sectioned tubes 214 .
  • the section S breach is dimensioned so that the secondary water flows into the vessel in a monitored manner, as indicated before.
  • the water present in the upper portion 211 spills out into the portion 212 a of the water box.
  • the latter is hydraulically connected to the inlet 13 of the vessel 10 , which enables the water to reach the overmelting metallic layer by descending through the downcomer 16 , thereby conferring the above-mentioned advantages.
  • a hole 215 for the tight passage of the control wires 217 b of the explosive device 216 shall be created in a wall of the heat generator 210 .
  • these control wires 217 b have one end accessible from outside the steam generator 210 to trigger the explosion.
  • These wires 217 b are installed during the set-up of the explosive device 216 .
  • the safety system comprises, besides the explosive plug 216 a , a thermowell, a magnetic connector and a magnetic exciter to trigger the explosion.
  • the thermowell has a portion which extends inside the steam generator 210 up to the explosive plug 216 a . This portion comprises a magnetic contactor and a wire connecting the magnetic contactor to the explosive plug 216 a .
  • the thermowell has a portion accessible from outside the steam generator 210 . This portion carries or is accessible from a magnetic exciter configured so as to activate the contactor. When the contactor is activated, it triggers the explosion of the explosive plug 216 a.
  • thermowell is preferably made of an a magnetic material.
  • An advantage of this solution is to avoid a wire passing through a wall of the steam generator 210 which simplifies sealing of the system.
  • control wires 216 b of the uppermost tubes 214 ′ shall remain accessible during the set-up of the devices placed at a lower level.
  • the explosive device 216 may be placed during the manufacture of the steam generator 210 . Alternatively, this solution may also be deployed on steam generators of plants in activity. For this purpose, it is proceeded with an operation of plugging a tube 214 or several tubes 214 already existing with an explosive plug 216 a.
  • This embodiment has the advantage of introducing no additional element into the steam generator 210 .
  • the explosive device is integrated into one of the tubes existing in conventional steam generators 210 .
  • FIG. 6C An example of an explosive device 216 is illustrated in FIG. 6C .
  • a tube 214 ′ sealed by an explosive plug 216 a is represented.
  • the explosive plug 216 a comprises a body 216 c inside which a main charge 216 d and at least one portion of a detonator 216 e are accommodated.
  • the detonator 216 e is in contact with the charge 216 d .
  • the body 216 c is made of a material transmitting the exploiting or comprises such a material.
  • One or several wire(s) 216 b connect the detonator 216 e to a triggering circuit accessible from outside the steam generator 210 .
  • a protective envelope 216 f isolates the detonator and the charge.
  • FIG. 6B illustrates, at the right-side portion, another alternative embodiment of the explosive device 216 .
  • an open-through passage channel 218 is provided, formed in the plate 213 with tubes, and setting the secondary water enclosed in the upper portion 211 and the primary water enclosed in the lower portion 212 of the water box, preferably the portion 212 a connected to the inlet 13 of the vessel 10 , in communication.
  • This passage channel 218 is sealed by an explosive device 216 .
  • this explosive device 216 may be identical to the previously-described explosive plug 216 a.
  • section S breach is defined by the initial section of the channel 218 .
  • this channel 218 section is perfectly controlled. This allows monitoring the velocity and the duration of the flow of the secondary fluid inside the vessel 10 more accurately.
  • the explosive load must be large enough to entirely extract the plug 216 off the channel 218 .
  • the same steam generator 210 may comprise explosive devices 216 of different types, as illustrated in FIG. 6B . Most often, the same steam generator 210 will comprise one single explosive device 216 or several explosive devices 216 of the same type.
  • FIG. 7 illustrates, in perspective view, the solution of the embodiment of FIGS. 5A and 5B .
  • the core 1 of the reactor is shown, with the vessel 10 whose bottom 12 contains the corium 70 bath.
  • a booster 110 to pilot and increase the pressure of the primary circuit 100 is also illustrated.
  • the vessel 10 For each steam generator 210 , the vessel 10 is fed via two inlet pipes. On each of these inlet pipes, a pump 101 , 102 is disposed between the steam generator 210 and the vessel 10 to make the fluid of the primary circuit 100 circulate.
  • These pumps 101 , 102 lie on the passage of the fluid 800 derived from the secondary circuit 200 upon triggering of the explosive device 216 .
  • the pumps 101 , 102 are of the immersed rotor type. Indeed, the rotors of these pumps lie vertically lower than the fluid passage circuit.
  • This pump type allows avoiding the presence of a “U”-shaped branch in the pipe connecting the steam generator 210 to the inlet 13 of the vessel 10 .
  • This allows facilitating the liquid flow by gravity, down to the cold portion of the vessel 10 , of the water derived from the secondary circuit 200 .
  • this gravity flow along the downcomer 16 improves the efficiency of cooling of the liquid metal layer 72 at the origin of the piercing of the vessel 10 by focusing effect.
  • the solution, illustrated in FIG. 7 has a significant advantage.
  • FIG. 7 also illustrates spraying in the form of a jet (spray) 803 that occurs upon expansion of the secondary water into the primary circuit 100 upon break-up of the fluidic containment barrier.
  • a jet spray
  • the steam created by the secondary water tends to propagate preferably on the cold side down to the downcomer 16 , rather than rising through the set of tubes 214 of the steam generator 210 and then descending and returning back to the vessel 10 on the hot side 14 , which promotes cooling down of the liquid metal layer 72 at the origin of the piercing of the vessel 10 by focusing effect.
  • This cooling is not as efficient as a purely liquid flow by gravity by running off, since it is then a steam and spray mixture that comes into contact with the entire metal surface present in the downcomer 16 .
  • a primary pump geometry with an immersed rotor, without any “U”-shaped branch as illustrated in FIG. 7 and mentioned hereinabove, is therefore preferred to obtain an optimum water injection efficiency from a break-up of a tube 214 of the steam generator 210 , since the purely liquid flow by gravity is favoured.
  • the invention provides a reliable and robust solution to considerably improve the safety of a PWR-type nuclear reactor, in particular in case of loss of coolant from the primary circuit.
  • the communication point between the primary circuit and the secondary circuit is selected such that the propagation of secondary water towards the primary circuit takes place almost exclusively on the cold branch side of the primary circuit.
  • the water of the steam generators will follow the primary cold branches before flowing by gravity in the downcomer, where piercing of the vessel by focusing effects takes place.
  • the reactor 1 comprises several inlets and several outlets.
  • it also comprises several steam generators 210 .

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
US17/443,991 2020-07-29 2021-07-29 Reactor and safety method for a reactor for the event of a meltdown of the core Pending US20220037043A1 (en)

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FR2008046 2020-07-29
FR2008046A FR3113173B1 (fr) 2020-07-29 2020-07-29 Réacteur et Procédé de sécurité pour réacteur en cas de fusion du cœur

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Citations (7)

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Publication number Priority date Publication date Assignee Title
US3919940A (en) * 1972-08-25 1975-11-18 Siemens Ag Explosive-activated plug
US3927791A (en) * 1974-08-05 1975-12-23 Welcome D Hershberger Fusible plug
US4692297A (en) * 1985-01-16 1987-09-08 Westinghouse Electric Corp. Control of nuclear reactor power plant on occurrence of rupture in coolant tubes
US5652775A (en) * 1995-04-11 1997-07-29 Framatome Method and device for detecting and monitoring perforation of the vessel bottom head of a nuclear reactor
US20120328067A1 (en) * 2011-06-22 2012-12-27 Kabushiki Kaisha Toshiba Nuclear power plant
EP3067895A1 (en) * 2015-03-09 2016-09-14 Hitachi-GE Nuclear Energy, Ltd. Primary containment vessel
US20170154692A1 (en) * 2014-07-04 2017-06-01 Retech Co., Ltd. Porous cooling block for cooling corium and corium cooling apparatus including same, and corium cooling method using same

Family Cites Families (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2763168B1 (fr) 1997-05-06 1999-11-05 Commissariat Energie Atomique Reacteur nucleaire a eau, dont la cuve contient un dispositif de recuperation du coeur apres sa fusion accidentelle
FR2922678A1 (fr) 2007-10-22 2009-04-24 Commissariat Energie Atomique Reacteur nucleaire a refroidissement ameliore en situation d'accident
CN104167229B (zh) * 2014-04-24 2017-03-29 国核华清（北京）核电技术研发中心有限公司 非能动安全壳冷凝水注入系统

Patent Citations (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3919940A (en) * 1972-08-25 1975-11-18 Siemens Ag Explosive-activated plug
US3927791A (en) * 1974-08-05 1975-12-23 Welcome D Hershberger Fusible plug
US4692297A (en) * 1985-01-16 1987-09-08 Westinghouse Electric Corp. Control of nuclear reactor power plant on occurrence of rupture in coolant tubes
US5652775A (en) * 1995-04-11 1997-07-29 Framatome Method and device for detecting and monitoring perforation of the vessel bottom head of a nuclear reactor
US20120328067A1 (en) * 2011-06-22 2012-12-27 Kabushiki Kaisha Toshiba Nuclear power plant
US20170154692A1 (en) * 2014-07-04 2017-06-01 Retech Co., Ltd. Porous cooling block for cooling corium and corium cooling apparatus including same, and corium cooling method using same
EP3067895A1 (en) * 2015-03-09 2016-09-14 Hitachi-GE Nuclear Energy, Ltd. Primary containment vessel

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FR3113173B1 (fr) 2022-07-29
FI3945530T3 (en) 2023-11-02
PL3945530T3 (pl) 2024-02-12
CN114068045A (zh) 2022-02-18
FR3113173A1 (fr) 2022-02-04
EP3945530B1 (fr) 2023-08-23

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